A process heat exchanger (PHE) transfers the heat generated from a nuclear reactor to a sulfur-iodine hydrogen production system in the Nuclear Hydrogen Development and Demonstration, and was subjected to very high temperature up to . An evaluation of creep-fatigue damage, for a prototype PHE, has been carried out from finite element analysis with the full three dimensional model of the PHE. The inlet temperature in the primary side of the PHE was with an internal pressure of 7 MPa, while the inlet temperature in the secondary side of the PHE is with internal pressure of 4 MPa. The candidate materials of the PHE were Alloy 617 and Hastelloy X. In this study, only the Alloy 617 was considered because the high temperature design code is available only for Alloy 617. Using the full 3D finite element analysis on the PHE model, creep-fatigue damage evaluation at very high temperature was carried out, according to the ASME Draft Code Case for Alloy 617, and technical issues in the Draft Code Case were raised.
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October 2011
Research Papers
An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant
Hyeong-Yeon Lee,
e-mail: hylee@kaeri.re.kr
Hyeong-Yeon Lee
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
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Kee-Nam Song,
Kee-Nam Song
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
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Yong-Wan Kim,
Yong-Wan Kim
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
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Sung-Deok Hong,
Sung-Deok Hong
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
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Hong-Yune Park
Hong-Yune Park
AD-Solution Co., Ltd.
, 1101 Hanjin Officetel 535-5, Bongmyoung-dong Yusong-gu, Daejeon 305-301, Republic of Korea
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Hyeong-Yeon Lee
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Koreae-mail: hylee@kaeri.re.kr
Kee-Nam Song
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
Yong-Wan Kim
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
Sung-Deok Hong
Korea Atomic Energy Research Institute
, 150 Dukjin-dong, Yusong-gu, Daejeon 305-353, Republic of Korea
Hong-Yune Park
AD-Solution Co., Ltd.
, 1101 Hanjin Officetel 535-5, Bongmyoung-dong Yusong-gu, Daejeon 305-301, Republic of KoreaJ. Pressure Vessel Technol. Oct 2011, 133(5): 051208 (7 pages)
Published Online: July 14, 2011
Article history
Received:
May 10, 2010
Revised:
January 4, 2011
Online:
July 14, 2011
Published:
July 14, 2011
Citation
Lee, H., Song, K., Kim, Y., Hong, S., and Park, H. (July 14, 2011). "An Evaluation of Creep-Fatigue Damage for the Prototype Process Heat Exchanger of the NHDD Plant." ASME. J. Pressure Vessel Technol. October 2011; 133(5): 051208. https://doi.org/10.1115/1.4003466
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